Equations and results are given for various methods of solution of the one-dimensional transport equation for one energy group in plane geometry with inelastic scattering and an isotropic source. After considerable investigation, a matrix method of solution was found to be faster and more stable than iteration procedures. A description of the code is included which allows for up to 24 regions, 250 points, and 16 angles such that the product of the number of angles and the number of points is less than 600.

The wave like pattern, observed in dislocation dipoles of uniform spacing during annealing, which starts from the ends of the dipole and gets damped toward the centre, has been attributed to controlled vacancy migration. A theory has been set-up to give activation energy for the process, 60,700 + 2,000 cal/mole. This value has been compared with an independent study of pipe diffusion, in which a prismatic loop inside the foil is connect to both surfaces of the foil by screw dislocation.

This document contains information regarding the effects of thermal effluents on the Columbia River during September 1970. Thermal effluents increase the gas saturation in water leading to the mortality of fishes. The ``gas bubble`` disease has been considered to be mostly a physical phenomenon due to the differences between the sum of the individual tensions of the gasses dissolved in water and the hydrostatic pressure. A drop in hydrostatic pressure was shown to induce bubble formation in the fish tissues. It has been recognized that chronic high gas saturations such as exist seasonally in the Columbia River also create gas embolisms and inflict heavy mortalities on anadramous fishes.

This report presents a review of current 100-K Plant liquid waste disposal practices. The report s divided into two sections with Section I consisting of a general description of the Plant facilities to dispose of liquid wastes by ground disposal or by direct discharge to the Columbia River. Section II further appraises liquid waste disposal practices by examining each material that is used in any significant degree in Plant operations. For ease of presentation in Section II, the materials are grouped into general categories of usage with two primary considerations reviewed for each material, i.e., (a) the storage and supply arrangement with emphasis on provisions or safeguards to prevent accidental discharge and (b) the specific application of the material in the process, manner of usage, and final disposition. The report should be viewed as only an informal source of data to aid in the future preparation (by others) of a comprehensive environmental control plan document. Suggestions as to refinements, additions, or corrections are solicited.

This final report details production test-176, the primary purpose of which was to provide a quantitative comparison of fuel element 8001 aluminum alloy cladding corrosion in cooling water containing 0.5 and 1.0 ppm sodium dichromate inhibitor. Secondary purposes were to provide information on cladding corrosion as a function of temperature and as a function of time at both inhibitor concentrations. The primary purpose was well fulfilled: Equations were developed to describe and predict fuel element weight losses at both dichromate concentrations and the effect of dichromate concentration on localized corrosion was clearly established. Little effect of dichromate concentration on localized corrosion was observed when fuel cladding temperatures were below 115--120 C but above these temperatures the localized corrosion definitely was more severe in coolant containing 0.5 ppm inhibitor. The bottom rows of fuel element supports rapidly corroded away at the higher temperatures which caused a further increase in local temperatures due to flow imbalances and this in turn accelerated the localized corrosion. Because the higher dichromate concentration reduced the amount of support corrosion, 1.0 ppm dichromate should be employed to control localized corrosion whenever cladding temperatures are expected to be above 120 C for long periods of time. These tests …

In this semiannual issue the single pass reactor and water plant data are shown for the six-month period January through June, 1970, together with data for the three preceding six-month periods.

This document presents a Preliminary Measurement Data Requirement List (MDRL), Data Item C-103, for the NERVA E-1 Ground Test Engine. The MDRL presents 628 parameters/channels for non-nuclear engine hardware. An estimate of 472 parameters/channels for NSS hardware was made jointly by ANSC/WANL, since detailed NSS requirements have not been defined to date. Therefore, the total engine parameters/channels is 1100. This is based on the ANSC Design Baseline Flight Engine defined by drawings 1137400C and 1137401D, since a baseline ground test engine has not yet been defined. This submittal is an extra scope item not included in the CY 1970 Contractual Work Statements, but will be used in conjunction with the Preliminary NERVA Operational Flight Engine MDRL, dated September 1970 which was in compliance with the Project 117 CY 1970 Contractual Work Statement paragraph f5d. This document provides initial definition of measurement system design requirements to provide direction for instrumentation and wiring harness design and to provide a baseline for performance of Measurement System design and analysis activities related to the ground test engines.

The Quality Plan for the SNAP-27 Follow-On Program describes the manner in which the Isotope Power Systems Operation of the General Electric Space Division will control product quality. NASA NHB5300.4 (1B) and AEC QASL-SNAP-1 and 2 have been used as guides in the development of this plan and, upon approval by the AEC, this plan will serve as a policy document to be utilized in implementing the SNAP-27 Follow-On Quality Program.

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The cyclic corrosion resistance capability of an R-1 type periphery featuring a multiple layer Z-liner thermalized rerolled pyrofoil wrapper was experimentally measured. This test employed an SX-5 graphite core and simulated fuel elements.

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The geology and hydrology of the Hanford Reservation are reviewed, with emphasis on ground water flow, to identify those areas that should be restricted from unconditional release due to radionuclide cortamination or radioactive waste storage as well as those areas that would have no hydrological restrictions. The effects of the discharge of large quantities of cooling water from the radiochemical plants on ground water flow were also evaluated. (CH)

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Two 90UC--10ZrC fueled converters, IC-13 of Mark VI configuration and IC- C3 of Mark VIIB configuration, were examined in hot cell after in-pile operation. IC-3 operated for 4395 hours at an average emitter temperature of 1675 deg C as a converter test and then for 2945 hours at an average emitter temperature of ~1500 deg C as a fuel irradiation test; the average fuel burnup achieved was 2.5 x 10/ sup 20/ fission/c.c. IC-C3 operated 5445 hours at an average emitter temperature of 1670 deg C as a converter test; the average fuel burnup achieved was 5 x 10/ sup 19/ fission/c.c. The carbide fuel contained 4 wt % tungsten and had a C/U atom ratio of 1.05. Other unique features for the converter components were fluoride tungsten claddings of controlled fluorine contents (18 ppM for IC-I3 and 19 ppM for IC-C3), and the presence of a high temperature seal and a graphite sorption cesium reservoir in IC-C3 converter. The results obtained on fuel swelling, emitter deformation, fuel-cladding interaction and microstructures of various converter components are presented. Solutions to the problem areas encountered are recommended. (auth)

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